UNLOADING AND STORAGE OF SPENT NUCLEAR FUEL DURING DISMANTLING OPERATIONS OF FRENCH NUCLEAR SUBMARINES

2006 ◽  
pp. 401-402
Author(s):  
B. ROBIN
Keyword(s):  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
And Storage

Experience With Damaged Spent Nuclear Fuel at U.S. DOE Facilities

2006 ◽  
Author(s):  
Brett Carlsen ◽  
Denzel Fillmore ◽  
Roger L. McCormack ◽  
Robert Sindelar ◽  
Timothy Spieker ◽  
...  
Keyword(s):  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
National Laboratory ◽  
Equipment Design ◽  
Lessons Learned ◽  
Nuclear Fuels ◽  
Idaho National Laboratory ◽  
Safe Storage ◽  
And Storage ◽  
Storage Facilities

This report summarizes some of the challenges encountered and solutions implemented to ensure safe storage and handling of damaged spent nuclear fuels (SNF). It includes a brief summary of some SNF storage environments and resulting SNF degradation, experience with handling and repackaging significantly degraded SNFs, and the associated lessons learned. This work provides useful insight and resolutions to many engineering challenges facing SNF handling and storage facilities. The context of this report is taken from a report produced at Idaho National Laboratory and further detailed information, such as equipment design and usage, can be found in the appendices to that report.

Burnup Credit in the Criticality Safety Analysis of Spent Fuel in Transportation and Storage Systems

2013 ◽  
Author(s):  
Vladyslav Soloviov
Keyword(s):  
Nuclear Fuel ◽  
Beta Decay ◽  
Spent Nuclear Fuel ◽  
Storage Systems ◽  
Multiplication Factor ◽  
Spent Fuel ◽  
Neutron Multiplication ◽  
Initial Fuel ◽  
Effective Neutron ◽  
And Storage

In this paper accounting of spent nuclear fuel (SNF) burnup of RBMK-1000 only with actinides has been performed. The following characteristics were analyzed: initial fuel enrichment, burnup fraction, axial burnup profile in the fuel assembly (FA) and fuel weight. As the results show, in the first 400 hours after stopping the reactor, there is an increase in the effective neutron multiplication factor (keff) due to beta decay of 239Np into 239Pu. Further, from 5 to 50 years, there is a decrease in keff due to beta decay of 241Pu into 241Am. Beyond 50 years there is a slight change in the criticality of the system. Accounting for nuclear fuel burnup in the justification of nuclear safety of SNF systems will provide an opportunity to increase the volume of loaded fuel and thus significantly reduce technology costs of handling of SNF.

Recent Development of Code Case on Use of Ductile Cast Iron for Transport and Storage Cask for Spent Nuclear Fuel

2008 ◽  
Author(s):  
Taku Arai ◽  
Toshiari Saegusa ◽  
Roland Hueggenberg
Keyword(s):  
Fracture Toughness ◽  
Cast Iron ◽  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Fatigue Curve ◽  
External Pressure ◽  
Ductile Cast Iron ◽  
Fracture Toughness Test ◽  
Technical Basis ◽  
And Storage

Code Case N-670 “Use of Ductile Cast Iron Conforming to ASTM A874/A 874M-98 or JIS G5504-1992 for Transport Containments, Section III, Division 3” which permits use of ductile cast iron for transport containments of spent nuclear fuel was revised to the Code Case N-670-1, “Use of Ductile Cast Iron Conforming to ASTM A874/A 874M-98 or JIS G5504-2005 for Transport and Storage Containments, Section III, Division 3”. Items revised were as follows: (a) Scope was expanded to use for transport and storage, and changed to conform year edition of JIS G5504, (b) The elongation requirement was deleted form the code case to reflect the change of year edition of JIS G5504, (c) Temperature condition of −40 °C was clearly provided for fracture toughness test, (d) Design fatigue curve was re-established, (e) External pressure chart was re-established. Technical basis of the revised code case are described in this paper.

scholarly journals Modeling of objects for reception and storage of spent nuclear fuel

2019 ◽  
Vol 378 ◽  
pp. 012110
Author(s):  
P V Yakovlev ◽  
V M Piskunov ◽  
V A Lebedev ◽  
N N Panasenko
Keyword(s):  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
And Storage
Sign in / Sign up

Export Citation Format

Share Document